Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor
Zhu, GF; Zou, Y; Xu, HJ; Dai, Y; Li, MH; Yan, R; Xu, HJ (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
2015
发表期刊PROGRESS IN NUCLEAR ENERGY
ISSN0149-1970
卷号83页码:374—386
文章类型期刊文献
摘要Thorium blanket fuel is investigated in Pebble Bed Fluoride salt-cooled High temperature Reactor (PB-FHR) with 19.9 at% U-235 seed fuel to improve the utilization of uranium fuel. Uranium fuel utilization is optimized with lots of parameters, such as graphite-to-thorium atom ratio (C/Th), graphite-to-uranium atom ratio (C/U), discharge burnup of thorium and uranium, and the dimension of the seed/blanket region. It is found that the equivalent discharge burnup, defined as total released energy over the mass of uranium, could be improved to around 265 MWd/kgU, which is 20% higher than discharge burnup using pure uranium fuel. In equilibrium state, the temperature reactivity coefficients of fuel and coolant are both negative. Other properties such as radial power peak factor, life of reflector, in-pile residence time of thorium pebble and radioactive waste are analyzed. Finally, baseline design parameters are recommended for further thermal-hydraulic analysis and TRISO fuel performance. (C) 2015 Elsevier Ltd. All rights reserved.
关键词Light-water Reactors Fuel Design
语种英语
WOS记录号WOS:000358468300039
引用统计
文献类型期刊论文
条目标识符http://ir.sinap.ac.cn/handle/331007/25094
专题中科院上海应用物理研究所2011-2018年
通讯作者Xu, HJ (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China.
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Zhu, GF,Zou, Y,Xu, HJ,et al. Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor[J]. PROGRESS IN NUCLEAR ENERGY,2015,83:374—386.
APA Zhu, GF.,Zou, Y.,Xu, HJ.,Dai, Y.,Li, MH.,...&Xu, HJ .(2015).Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor.PROGRESS IN NUCLEAR ENERGY,83,374—386.
MLA Zhu, GF,et al."Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor".PROGRESS IN NUCLEAR ENERGY 83(2015):374—386.
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